ML023030433
| ML023030433 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/25/2002 |
| From: | Lopriore R Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-02-001, BYRON 2002-0110 | |
| Download: ML023030433 (6) | |
Text
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Exelon Generation Company, LLC Byron Station 4450 North German Church Road Byron, IL 61010-9794 wwwexekoncorp com Nuclear October 25, 2002 LTR:
BYRON 2002-0110 File:
1.10.0101 United States Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Byron Station Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Byron Station Unit 2 Response to NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity" On March 18, 2002, the NRC issued NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity". This bulletin requires that the following information be submitted to the NRC within 30 days after plant restart following the next inspection of the reactor pressure vessel head to identify any degradation:
the inspection scope and results, including the location, size, and nature of any degradation detected; and the corrective actions taken and the root cause of the degradation.
Pursuant to 10 CFR 50.54, "Conditions of Licenses," paragraph (f), Attachment 1 to this letter provides the Byron Station Unit 2 30-day response. This response is due to the NRC by November 6, 2002.
ACA )
V.
October 25, 2002 U.S. Nuclear Regulatory Commission Page 2 If you have any questions or desire additional information regarding this letter, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Re
- ctfully, Ric ard P. Lopri e Site Vice Presid nt Byron Nuclear Generating Station RPL/MR/rah
Enclosures:
, Byron Station Unit 2 Response to NRC Bulletin 2002-01 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector-Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
STATE OF ILLINOIS COUNTY OF OGLE IN THE MATTER OF
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)
EXELON GENERATION COMPANY, LLC BYRON STATION UNIT 2
SUBJECT:
Docket Numbers
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STN 50-455 Byron Station Unit 2 Response to NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity" AFFIDAVIT I affirm that the content of this transmittal is,ttq pand correct to the best of my knowledge, information and belief.
,'ichard P. 0,6,ý'riore Site Vice P*;esident Byron Nuclear Generating Station Subscribed and sworn to before me, a Notary Public in and for the State above named, this S
day of C) C 5: :-ýl
,20 o07 Notary Public 60FFCIALSEAV Patricia Hayenga
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Nortary Public, State of "Inoln0s My Commission Expires 3/27/04
ATTACHMENT I Byron Station Unit 2 Response to NRC Bulletin 2002-01 "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity"
Attachment I Byron Station Unit 2 Response to NRC Bulletin 2002-01 On March 18, 2002, the NRC issued NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity".
This bulletin requires that the following information be submitted to the NRC within 30 days after plant restart following the next inspection of the reactor pressure vessel (RPV) head to identify any degradation:
- 2.
Within 30 days after plant restart following the next inspection of the reactor pressure vessel head to identify any degradation, all PWR addressees are required to submit to the NRC the following information:
- a.
the inspection scope and results, including the location, size, and nature of any degradation detected,
- b.
the corrective actions taken and the root cause of the degradation.
Byron Station Unit 2 Response
- a.
the inspection scope and results, including the location, size, and nature of any degradation detected,
Response
The following inspections were performed on the reactor pressure vessel (RPV) during refueling outage B2R10 in Fall 2002" Pre and post-outage VT-2 examinations of the accessible areas on top of the RPV head (i.e., control rod drive mechanism housings) were performed at normal reactor coolant system pressure No evidence of leakage, boric acid residue, or degradation of material due to corrosion was identified during these inspections VT-1 examinations were performed on the core exit thermocouple clamp assemblies. There was no evidence of erosion, corrosion, or wear of the bolting material, and there were no instances of bolting material degradation due to corrosion. These connections, which are disassembled each refueling outage, were specifically examined for leakage by VT-2 qualified personnel during unit startup and no abnormal conditions were identified.
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Attachment I A 100% bare metal RPV head examination was completed. This examination consisted of visual examinations (3600) of the RPV head vent penetration and all RPV head nozzles (78) at the annulus region to determine if any boric acid leakage was evident In addition, the bare metal RPV head was visually examined for general condition and to ensure no RPV head wastage was present. These examinations found no evidence of boric acid leakage from the nozzles or degradation of the RPV head
- b.
the corrective actions taken and the root cause of the degradation.
Response
There were no corrective actions taken or root cause investigations performed as no RPV degradation was identified.
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